Leak rate analysis of the Westinghouse Reactor Coolant Pump [electronic resource].

Published: Downey, Calif : Rockwell International, 1985.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description: Pages: 64 : digital, PDF file
Additional Creators: Rockwell International and United States. Department of Energy. Office of Scientific and Technical Information

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Summary

An independent analysis was performed by ETEC to determine what the seal leakage rates would be for the Westinghouse Reactor Coolant Pump (RCP) during a postulated station blackout resulting from loss of ac electric power. The object of the study was to determine leakage rates for the following conditions: Case 1: All three seals function. Case 2: No. 1 seal fails open while Nos. 2 and 3 seals function. Case 3: All three seals fail open. The ETEC analysis confirmed Westinghouse calculations on RCP seal performance for the conditions investigated. The leak rates predicted by ETEC were slightly lower than those predicted by Westinghouse for each of the three cases as summarized below. Case 1: ETEC predicted 19.6 gpm, Westinghouse predicted 21.1 gpm. Case 2: ETEC predicted 64.7 gpm, Westinghouse predicted 75.6 gpm. Case 3: ETEC predicted 422 gpm, Westinghouse predicted 480 gpm. 3 refs., 22 figs., 6 tabs.

Report Numbers

E 1.99:nureg/cr-4294
E 1.99: etec-drf-1714
etec-drf-1714
nureg/cr-4294

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Published through SciTech Connect.
07/01/1985.
"nureg/cr-4294"
" etec-drf-1714"
"TI85901844"
Boardman, T.; Lofaro, R.; Prevost, J.; Jeanmougin, N.

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